Hydraulic study

Mil. Matzner, B., and Biderman, R., Heat transfer and hydraulic studies for SNAP-4 fuel element geometries, Topical Rept. 1 and 2 Task XV of contract AT (30-3)-187, Columbia Univ. (1963). 

In the case of cephalosporin C extraction, chemical engineers played the major role in designing the large plant needed to meet the projected tonnage off-takes. Plant design was based on the results of resin evaluation and selection, hydraulic studies on the resin bead size and column dimensions, Cephalosporin C loading capacities,... 

Kreet P, Scheible OK, Venosa A (1986) Hydraulic Studies and Cleaning Evaluations of Ultraviolet Disinfection Units, J. Wat. Pollut. Control Fed. 58, No. 12 1129-1137. Kummer K (1990) Abwasserreinigung mit UV-Strahlern auf der Klaranlage der Stadt Cuxhaven, Berichte der Ahwassertechnischen Vereinigung e. V. 40 687-704. 

The absolute value enforces that the drag force acts opposite to the direction of fluid motion. Here Cd is the drag coefficient for the array, and it may differ in magnitude from the drag coefficients of isolated elements of the same form (see, e.g., discussions in [88,462, 505]). Note that this definition uses a factor 1/2, which is conventional for hydraulic studies. Many air studies exclude this factor as in equation (4.4) in Chapter 4. Cd is a function of stem Reynolds number, as well as canopy density, a. The dependencies of Cd are discussed below. 

Thomas, W. J., and M. Campbell, "Hydraulic Studies in a Sieve Plate Downcomer System, Trans. Inst. Chem. Eng. (London) 45, 1967, p. T53. 

Hydraulic studies were made to investigate the adequacy of. cooling in the reflector, safety rods, and fuel pieces. 

He then worked for the city in railroad and street projects. From 1906 he directed studies and designs for the New York City Board of Water Supply, and conducted hydraulic studies on the Catskill Water Supply System. From 1919 to 1927 he was assistant design engineer for the Holland Tunnel organization during which he proposed an important method of tunnel ring stress and silt pressure determination. 

SEFIDVASH, F., Status of the small modular fluidized bed light water nuclear reactor concept. Nuclear Engineering and Design, 167 pp. 203-214 (1996), SEFIDVASH, F., A preliminary thermal-hydraulic study of the fluidized bed nuclear reactor concept, Kerntechnik, 60, 1, pp.48-51 (1995). 

Hydraulic study of the fixed bed suspeuded core coucept... 

Hydraulic studies of a full size suspended mock-up core could be performed at an experimental hydraulic module made of transparent materials and using stainless steel balls to simulate fuel elements. Such module is to be provided with instrumentation to measure basic hydraulics parameters such as pressure drop as a function of coolant flow, velocity under different core configurations, etc. Videotaping of core operation could be provided in order to analyze performance of the suspended core under various simulated operating and accidental conditions. 

SEFIDVASH, F., A preliminary thermal-hydraulic study of the fluidized bed nuclear reactor concept, Kemtechnik 60, 1, pp.48-51, (1995). 

Thus, the different components of thermal-hydraulic studies are mainly ... 

Thermal-hydraulics design of the clad failure detection system. This system is used to detect possible clad failures in the fuel subassemblies while the plant is operating. Clad failure causes a release of fission products emitting delayed neutrons, that are transported to the hot plenum and to the detectors. In SPXl the detector itself is placed outside the hot plenum with a continuous poped sampling system for analysis of the primary sodium was set up other systems in which neutron detectors are placed near the intermediate heat exchanger inlets and enabled activity to be measured directly, have been studied. In both cases thermal-hydraulics studies were necessary to measure the hydraulic transfer functions between the various core... 

For the cold plenum, thermal-hydraulics studies should enable the thermal stresses in the structures (in particular the main vessel and the internal vessel) to be calculated, and the correct hydraulic supply to the primary pumps to be ensured. These studies should be carried out for the various operating states of the reactor symmetrical and assymmetrical vvith a secondary circuit out of operation, and for steady state conditions as well as transients. 

Hydraulic study of the cold plenum. For the cold plenum, hydraulic studies are particularly focused on the problems of supply to the primary pumps. For these to function correctly the supply should be homogeneous [8.18, 8.22]. Moreover, knowledge of the velocity field in the cold plenum is used to validate calculations. In hydraulic studies of this type, flow is similar if the Reynolds number is respected. In the reactor flows are fully turbulent, and flows obtained in scale models are accepted as being representative of reality as long as they are also fully turbulent. For practical reasons tests are carried out on scale models with Reynolds numbers > S.IO. ... 

Ninomiya, S., et. al. Thermal-hydraulic Study Aiming Compact Reactor Assembly, Proceedings of the International Conference on Fast Reactor and Related Fuel Cycles, Kyoto, Japan, 1991. 

The AGT 6 was involved in thermal-hydraulic studies of the primary system and the decay heat removal system by means of facilities such as COLCHIX 4 and JESSICA (Cadarache), THOR (Risley), NEPTUN, RAMONA and KIWA (Karlsruhe) and ILONA (Bensberg). In addition, R D was conducted on the thermal environment of the cover gas... 

Further experlmiatal thermal hydraulic studies are planned to datesUini the flow behavior and transient temperatures to be expected as a C0iMie< UettCe of partial plugging of flow channels These studies will be pirfsfaied by use of full scale mockup of the MPR process tube ... 

As shown in the sketch of Fig. 7.1, the fuel salt flows from the bottom to the top of the core cavity (note the absence of in-core solid matter). In preliminary designs developed in relation to calculations, the core of the MSFR is a single compact cylinder (2.25 m high x 2.25 m diameter) where the nuclear reactions occur within the liquid fluoride salt acting as fuel and as coolant. Thermal-hydraulic studies performed in the frame of the EVOL project have shown that a toms-shaped core (see Fig. 7.1) improves thermal flow (Laureau et al., 2013 Rouch et al., 2014 Laureau, 2015c). 

Currently, in addition to performing fundamental studies on various salts, facilities for natural-circulation—based thermal hydraulic studies and corrosion studies under an active molten salt (using Thp4 and natural UFq) environment are being commissioned. A schematic of the same is shown in Fig. 15.31. 

Section 2 presents the assumptions and requirements upon which the INEL concept was developed. Section 3 contains an overview of the reactor concept. Section 4 lists the conclusions and recommendations. Most of the technical details and discussions are contained in the appendices. The first task was to examine plutonium destruction rates and isotopics for different neutron spectra, as discussed in Appendix A. This study lead to the adoption of a thermal reactor concept instead of reactors with fast or epithermal neutron spectra. The second task was to study the addition of seed materials for selfprotection from materials diversion. Appendix B illustrates that fission products provide the best. self-protection, and seed materials are not needed for the INEL concept. Various fuel types were investigated and are described in Appendix C. The core neutronics studies presented in Appendix D and thermal-hydraulics studies pre.sented in Appendix E were performed concurrently. An evaluation of potential offsite radiation doses... 

Flow through each control valve usually has three difierent capacities maximum, normal, and miniinuin. Hydraulic study is usually either based on maximum flow or normal How. From hydraulic study (without pump or compressor available pressure drop of the control valve at cither condition (case 0) is calculated. The available control valve pressure drop at other two flow conditions (case 1 or 2) can be estimated by following equation ... 

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